References
- “ECCS Evaluation Models,” Title 10, Part 50, App. K, Code of Federal Regulations (June 1992).
- Relap5 Development Team, “RELAP5/MOD3 Code Manual,” NUREG/CR-5535, 7 vols., Idaho National Engineering Laboratory (1995).
- D. R. LILES, J. R. SPORE, T. D. KNIGHT, R. A. NELSON, M. W. CAPPIELLO, K. O. PASAMEHMETOGLU, J. H. MAHAFFY, L. A. GUFFEE, H. J. STUMPF, P. J. DOTSON, R. G. STEINKE, P. R. SHIRE, S. E. GRIER, and K. B. SHERWOOD, “TRAC-PFl/MODl, Correlations and Models,” NUREG/CR-5069, U.S. Nuclear Regulatory Commission (Dec. 1988).
- D. D. TAYLOR, M. M. GILES, G. A. JAYNE, C. M. MOHR, Jr., S. Z. ROUHANI, R. W. SHUMWAY, G. L. SINGER, M. A. STONE, and W. L. WEAVER III, “TRAC-BDl/MODl Code Manual,” NUREG/CR-3633, U.S. Nuclear Regulatory Commission (Apr. 1984).
- W. WULFF, H. S. CHENG, D. J. DIAMOND, and M. Khatib-Rahbar, “RAMONA-3B Code Manual,” NUREG/CR-3664, U.S. Nuclear Regulatory Commission (Jan. 1984).
- “Compendium of ECCS Research for Realistic LOCA Analysis,” NUREG-1230, U.S. Nuclear Regulatory Commission (Dec. 1988).
- G. LOOMIS, “Summary of the SEMISCALE Program,” NUREG/CR-4945, U.S. Nuclear Regulatory Commission (July 1987).
- C. NALEZNY, “Summary of the NRC’s LOFT Program Research Findings,” NUREG/CR-3005, U.S. Nuclear Regulatory Commission (Apr. 1985).
- W. SUTHERLAND, M. ALAMGIR, J. A. FINDLAY, and W. S. HWANG, “BWR FIST Phase II, Final Report,” NUREG/CR-4128, U.S. Nuclear Regulatory Commission (Oct. 1985).
- D. G. SCHUMACHER, T. ECKERT, and J. A. FINDLAY, “BWR Refill-Reflood Program-SSTF System Response Test Results,” NUREG/CR-2568, General Electric (Apr. 1983).
- J. GLOUDEMANS, “MIST: Final Report, Summary,” NUREG/CR-5395, Babcock & Wilcox (Apr. 1991).
- Y. Y. HSU, M. diMarzo, and K. ALMENAS, “UMCP Scaling Analysis and Methodology: Summary Compilation,” MDNE 060190 (June 1990).
- P. S. DAMERELL and J. W. SIMONS, “2D/3D Program Work Summary Report,” NUREG/IA-0126, Sec. 3, MPR Associates (June 1993).
- P. S. DAMERELL and J. W. SIMONS, “2D/3D Program Work Summary Report,” NUREG/IA-0126, Sec. 4, MPR Associates (June 1993).
- L. SHOTKIN and Y. KUKITA, “Implications of the Rig of Safety Assessment/AP600 High- and Intermediate-Pressure Test Results,” Nucl. Technol., 116, (Dec. 1996) ( to be published).
- NRC-04-95-039, U.S. Nuclear Regulatory Commission/Oregon State University (May 1995).
- M. ISHII, S. T. REVANKAR, R. DOWLATI, M. L. BERTODANO, I. BABELLI, W. WANG, H. POKHARNA, V. H. RANSOM, and R. VISKANTA, “Scientific Design of PUMA for GE SBWR,” NUREG/CR-6309, U.S. Nuclear Regulatory Commission (Apr. 1996).
- Technical Program Group, “Quantifying Reactor Safety Margins,” NUREG/CR-5249, U.S. Nuclear Regulatory Commission (Dec. 1989).
- B. E. BOYACK, I. CATTON, R. B. DUFFEY, P. GRIFFITH, K. R. KATSMA, G. S. LELLOUCHE, S. LEVY, U. S. ROHATGI, G. E. WILSON, W. WULFF, and N. ZUBER, “An Overview of the Code Scaling, Applicability, and Uncertainty Evaluation Methodology,” Nucl. Eng. Des., 119, 1 (1990).
- P. DAMERELL and J. SIMONS, “Reactor Safety Issues Resolved by the 2D/3D Program,” NUREG/IA-0127, MPR Associates (July 1993).
- M. YOUNG and J. SURSOCK, “Coordination of Safety Research for the B&W Integral System Test Program,” NUREG-1163, U.S. Nuclear Regulatory Commission (Mar. 1987).
- T. BOUCHER, M. diMarzo, and L. SHOTKIN, “Scaling Issues for a Thermal-Hydraulic Integral Test Facility,” NUREG/CR-0119, Vol. 3, p. 367, U.S. Nuclear Regulatory Commission (Apr. 1992).